ANDREA recalculation of operation history of VVER-440

Author

Heraltova, Lenka ; Frybort, Jan

Author_Institution

Fac. of Nucl. Sci. & Phys. Eng., Czech Tech. Univ. in Prague, Prague, Czech Republic

fYear

2014

fDate

12-14 May 2014

Firstpage

709

Lastpage

713

Abstract

Macrocode ANDREA has been developed in UJV Rez a.s. It is used for neutronic calculation of fuel batches. During its development, the code was verified and validated for reactors VVER-1000 and new version ANDREA 2.0 was validated also for VVER-440 reactors in year 2013. This paper describes process of validation of the ANDREA code for reactors VVER-440. Firstly, the new features implemented into the solver were tested by a simple benchmark, then a Full-Core benchmark for VVER-440 reactors was recalculated and finally real operational data from NPP Dukovany, Czech Republic were used to evaluate the ability to predict characteristics of fuel batches.

Keywords

fission reactor core control; fission reactor fuel; light water reactors; nuclear engineering computing; AD 2013; ANDREA code; ANDREA recalculation; Czech Republic; Macrocode ANDREA; NPP Dukovany; VVER-1000 reactors; VVER-440 operation history; VVER-440 reactors; fuel batches; neutronic calculation; Assembly; Benchmark testing; Fuels; Inductors; Pins; Power distribution; Temperature measurement; ANDREA; VVER-440; benchmark;

fLanguage

English

Publisher

ieee

Conference_Titel

Electric Power Engineering (EPE), Proccedings of the 2014 15th International Scientific Conference on

Conference_Location

Brno

Type

conf

DOI

10.1109/EPE.2014.6839508

Filename

6839508